The paper covers the results of VVER core reflooding studies in fuel assembly (FA) mockup of 126 fuel rod simulators with axial power peaking. The experiments were performed for two types of flooding. The first type is top flooding of the empty (steamed) FA mockup. | A study of different cases of VVER reactor core flooding in a large break loss of coolant accident EPJ Nuclear Sci. Technol. 2 3 2016 Nuclear Sciences . Bezrukov et al. published by EDP Sciences 2016 amp Technologies DOI epjn e2015-50005-9 Available online at http REGULAR ARTICLE A study of different cases of VVER reactor core flooding in a large break loss of coolant accident Yury Alekseevich Bezrukov Vladimir Ivanovitc Schekoldin Sergey Ivanovich Zaitsev Andrey Nikolaevich Churkin and Evgeny Aleksandrovich Lisenkov OKB GIDROPRESS 21 Ordzhonikidze Street Podolsk Moscow Region 142103 Russian Federation Received 29 April 2015 Received in final form 3 August 2015 Accepted 21 October 2015 Published online 15 January 2016 Abstract. The paper covers the results of VVER core reflooding studies in fuel assembly FA mockup of 126 fuel rod simulators with axial power peaking. The experiments were performed for two types of flooding. The first type is top flooding of the empty steamed FA mockup. The second type is bottom flooding of the FA mockup with level of boiling water. The test parameters are as follows the range of the supplied power to the bundle is from 40 to 320 kW the cooling water flow rate is from to kg s the maximum temperature of the fuel rod simulator is 800 C and the linear heat flux is from to kW m. The test results were used for computer code validation. 1 Introduction 2 Brief descriptions of experimental studies in western countries Loss of primary coolant accidents in pressurized water reactors VVER reactors in Russia and PWR reactors in the This section contains a brief description of some experimen- West belong to the most severe cases in the spectrum of tal studies performed in western countries. The background accidents in the nuclear power industry. The MCP guillotine of the studies of the structure of the steam-water flow in the break is considered to be the maximum design basis accident. rod bundle goes back to the
